1. NAME AND TITLE

ARMYL-N: Calculation of Transmission Factors for Neutrons from Nuclear Explosions.

2. CONTRIBUTOR

Department of Theoretical Studies, Central Armaments Laboratory, Arcueil, French Ministry of Defense through the OECD NEA Data Bank, Gif-sur-Yvette, France.

3. CODING LANGUAGE AND COMPUTER

FORTRAN IV; UNIVAC 1106.

4. NATURE OF PROBLEM SOLVED

ARMYL-N calculates the variation of the neutron dose transmission factor as a function of the thickness of flat shields of concrete, steel, or earth, for radiations occurring as a result of nuclear explosions.

5. METHOD OF SOLUTION

Invariant imbedding is used in ARMYL-N.

6. RESTRICTIONS OR LIMITATIONS

ARMYL-N is bound by the following limits:

Maximum number of energy groups - 10

Maximum number of angular groups - 7

There is no restriction on range.

7. TYPICAL RUNNING TIME

ARMYL-N uses 4 minutes on a UNIVAC 1108 for a maximum number of energy and angular groups.

8. COMPUTER HARDWARE REQUIREMENTS

ARMYL-N runs on a UNIVAC 1106 with 51 K words of 36 bits, 2 mag tape units for auxiliary storage and an on-line printer.

9. COMPUTER SOFTWARE REQUIREMENTS

A FORTRAN IV compiler is required.

10. REFERENCE

M. Marquie, "Neutron Dose Transmission Factors in Various Shields," ORNL-tr-4280, a translation of LCA 74 R 130, ETUDE 07.1, No. 283/DET (October 1974).

11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source codes and sample problem input and output.

12. DATE OF ABSTRACT

December 1981.